U.S. patent number 3,623,948 [Application Number 04/724,026] was granted by the patent office on 1971-11-30 for pressurized-water nuclear reactor.
This patent grant is currently assigned to The Babcock & Wilcox Company. Invention is credited to Erroll W. Dotson, John H. Kidwell, Gerald D. Lindstrom.
United States Patent |
3,623,948 |
Dotson , et al. |
November 30, 1971 |
PRESSURIZED-WATER NUCLEAR REACTOR
Abstract
A pressurized-water nuclear reactor wherein the incoming
relatively cool water entering the reactor is distributed for
temperature equalization and controlled flow through the reactor
core so as to minimize overheating of localized portions of the
core.
Inventors: |
Dotson; Erroll W. (Louisville,
OH), Kidwell; John H. (Alliance, OH), Lindstrom; Gerald
D. (North Benton, OH) |
Assignee: |
The Babcock & Wilcox
Company (New York, NY)
|
Family
ID: |
24908662 |
Appl.
No.: |
04/724,026 |
Filed: |
April 25, 1968 |
Current U.S.
Class: |
376/352; 376/399;
976/DIG.19 |
Current CPC
Class: |
G21C
1/08 (20130101); Y02E 30/40 (20130101); Y02E
30/30 (20130101) |
Current International
Class: |
G21C
1/00 (20060101); G21C 1/08 (20060101); G21c
015/24 () |
Field of
Search: |
;176/50,61,64,87 |
References Cited
[Referenced By]
U.S. Patent Documents
Primary Examiner: Sebastian; Leland A.
Assistant Examiner: Behrend; Harvey E.
Claims
What is claimed is:
1. In a pressurized-water nuclear reactor, walls defining an
upright pressure vessel of circular cross section and having upper
and lower end closures, a core shield of circular cross section
radially spaced inwardly of said vessel and defining an annular
passageway therebetween, said core shield being attached to said
pressure vessel in the upper end portion of said vessel and
extending downwardly to a position spaced above said lower end
closure, a reactor core positioned within the lower portion of said
core shield and forming a plenum chamber therebeneath, nozzle means
positioned in the upper portion of and extending through the wall
of said pressure vessel and said core shield above said core to
define a water outlet from said nuclear generator, the improvement
comprising means for directing a distributed flow of incoming water
to the lower end of said core for upward passage therethrough
including inlet means radially positioned in the wall of said
pressure vessel above said core and opening into said annular
passageway, baffle means for directing water flow downwardly into
said annular passageway, vane means positioned in said incoming
water flow path to impart a swirl to said water passing through
said plenum chamber, perforated plate means positioned between said
plenum chamber and the lower end of said core, and a vortex
inhibitor fixedly attached to the lower surface of the center
portion of said perforated plate means.
2. A pressurized water reactor according to claim 1 wherein said
nozzle means and said inlet means are circumferentially spaced
about said pressure vessel and are located at a substantially
common elevation.
3. A pressurized water reactor according to claim 1 wherein the
bottom closure is an inverted dome and said vane means are attached
to the internal surface thereof.
4. A pressurized water reactor according to claim 1 wherein said
baffle means are of inverted U-shape and are attached to said core
shield in flow alignment with each of said inlet means.
5. A pressurized water reactor according to claim 1 wherein said
perforated plate means includes a perforated inverted domed plate
circumferentially attached to the lower end portion of said core
shield and is spaced beneath said core.
6. A pressurized water reactor according to claim 5 wherein a
perforated plate baffle is positioned between the lower end of said
core and said perforated inverted domed plate.
7. A pressurized water reactor according to claim 5 wherein said
inverted domed plate is perforated with substantially equally
spaced openings of substantially equal area.
8. A pressurized water reactor according to claim 6 wherein the
openings in said perforated plate are of substantially uniform
area.
Description
This invention relates in general to a nuclear power reactor, and
more particularly to a nuclear reactor of the pressurized water
type wherein water is heated in passing through a reactor core
located in a pressure vessel.
In a pressurized water reactor, large volumes of water under high
pressure are forced through a reactor core to heat the water to a
predetermined temperature somewhat below the saturation temperature
corresponding to that pressure. Leaving the reactor vessel, the
heated water (known as primary fluid) is utilized to heat lower
pressure water (known as secondary fluid) so as to produce steam
which is usually superheated and supplied to prime movers for the
generation of electric energy. The water cooled in generating steam
is thereafter recycled to the pressurized reactor so as to reheat
the water and to continue the power generation cycle.
When a pressurized water reactor is used the temperature of the
high-pressure water leaving the reactor must be maintained at a
safe marginal temperature under the saturation temperature at the
corresponding pressure. As those skilled in the art will
understand, it is highly desirable to utilize as high a water
temperature leaving the reactor as possible while still minimizing
the generation of steam during heating of the water in the nuclear
core. The necessity for maintaining the pressurized water
temperature at a selected value is primarily for the safety of and
to protect the operation of the nuclear core. It will be understood
that any overheating, such as caused by excessive steam generation
in the pressurized water can cause overheating of the core elements
due to inadequate cooling. Such overheating is dangerous and might
result in damage to and/or destruction of the core.
To attain safe nuclear core operation, it is necessary to provide
proper distribution of water (primary fluid) flow to the core so as
to obtain desired flow rates to all parts of the core as well as to
equalize the temperature throughout all parts of the water entering
the core.
In accordance with the present invention, we provide structure for
proper distribution of water entering the nuclear core of the
reactor. Since the recycled water returned to the nuclear core may
enter the reactor vessel through a plurality of inlets, the inlets
are arranged to open into an annular space enclosing the reactor
core and are baffled to direct the water downwardly into a lower
plenum chamber. The pressurized water entering and passing through
the plenum chamber is given a swirling movement by the use of vanes
interposed in its flow path. The swirling action of the mass of
water mixes such water so as to equalize temperatures therein and
to distribute the water throughout the plenum chamber. The water
leaving the plenum chamber passes upwardly through a perforated
inverted domed plate which further distributes the entering water
and discharges into a second plenum chamber with the water
thereafter passed upwardly through a perforated flat plate for
controlled introduction into the multiple parallel-flow passageways
of the reactor core.
Of the drawings:
FIG. 1 is an elevation, partly in section of a pressurized-water
reactor constructed and arranged according to the present
invention;
FIG. 2 is a schematic plan view of FIG. 1 taken on the line 2--2 of
FIG. 1;
FIG. 3 is an enlarged view of a portion of the apparatus shown in
FIG. 1;
FIG. 4 is an enlarged section of a portion of the apparatus shown
in FIG. 1; and
FIG. 5 is a section taken on line 5--5 of FIG. 4.
In the illustrated embodiment of the invention a pressurized water
reactor is provided with a substantially upright pressure vessel 10
of circular cross section having a closed top 11 and an inverted
domed bottom closure 12. Internally of the pressure vessel is
positioned a core shield 13 which is laterally spaced from and
coaxial with the inner surface of the pressure vessel wall. The
core shield is attached to and suspended from the upper end portion
of the pressure vessel and extends downwardly to a position 14
upwardly spaced from the lower inverted domed closure 12 of the
pressure vessel.
As shown, the upper portion of the pressure vessel is provided with
four circumferentially spaced water inlet nozzles 15 which
discharge into an annular passageway 16 defined between the core
shield and the pressure vessel walls. At this same upper level and
circumferentially spaced from the inlets are positioned a pair of
water outlet nozzles 20 which extend through the pressure vessel
and the annular space to open into the internal space 21 defined by
the core shield 13.
The reactor core 22 is positioned in the lower end portion of the
core shield and is supported directly thereon by a suitable
structure 23. Thus, the flow of water is from the inlet nozzles 15
downwardly through the annular passageway 16 between the pressure
vessel wall and the core shield 13 to a plenum chamber 24
positioned in the lower portion of the pressure vessel. The water
thereafter reverses direction and flows upwardly through the core
22 into the upper portion of the core shield and through suitable
openings therein interconnected with the outlet nozzles 20.
In accordance with proper safety provisions, the pressure vessel is
provided with a row of circumferentially, equally spaced brackets
25 extending inwardly from the pressure vessel wall into alignment
with a flange 26 attached to the shield and forming part of the
structure 23 supporting the core 22. The brackets are ordinarily
out of contact with any portion of the core shield or the associate
core-supporting structure. The brackets 25 are intended to prevent
unusual swaying of the core shield 13 as might be caused by
earthquakes or other external influences on the reactor pressure
vessel and furthermore provide a support for the core in case of
accidental overheating which would weaken the supporting structure
of the core.
In the construction so far described the reactor core 22 is
essentially surrounded by pressurized water, with the relatively
cool water moving downwardly through the annular passageway 16 and
then upwardly through the core for heating and through the central
portion of the pressure vessel. Since it is highly desirable to
have the maximum amount of sensible heat in the heated pressurized
water for use in external heat exchangers (not shown) for the
generation of steam in the secondary fluid and at the same time
provide a temperature difference between the pressurized water
operating and saturation temperatures at the prevailing pressure to
protect the nuclear core, it is essential to provide a
substantially uniform water flow and temperature distribution to
and through the core 22. The core is of known type wherein a
plurality of upright fuel rods are spaced throughout the core cross
section and a plurality of parallel water flow passageways of
substantially equal cross-sectional flow area are distributed
throughout the core, to cool the fuel rods and to heat the
water.
In accordance with the invention, an inverted U-shaped baffle 27 is
positioned on the core shield 13 in alignment with each of the
water inlet nozzles 15 to direct incoming water flow downwardly in
the annular passageway 16. It has been found that such baffles are
instrumental in improving peripheral flow distribution and assuring
maximum effectiveness of the swirl vanes hereinafter described. A
condition of unbalance in incoming water flow may be caused by many
circumstances, such as pump malfunction and the like. Under some
conditions, such as a pump failure in one of the four lines leading
to the inlet nozzles, the maldistribution of water entering the
core could have serious consequences on the core, unless baffles 27
and the water distribution arrangement hereinafter described were
in service.
A series of inclined vanes 30 are attached to the lower inner
surface of the domed bottom closure 12 to impart a swirl to the
water entering the lower portion of the pressure vessel. The vanes
are directly welded to the inverted domed bottom closure 12 of the
pressure vessel and are inclined at an angle to a radial plane
passing through the vertical axis of the vessel. It will be
understood that the water passing downwardly through the annular
passageway 16 will encounter the vanes so that the incoming stream
will be caused to swirl in the plenum 24 or bottom portion of the
pressure vessel. It will be understood that the vanes may be
straight or curved and may be positioned in the annular passageway
16 between the core shield and the pressure vessel walls or could
be positioned intermediate the location shown and the annular
passageway 16. In the present instance it has been found desirable
to position the vanes 30 directly on the inverted domed wall of the
bottom closure 12 for ease of attachment and to facilitate
installation.
With the vanes 30 positioned adjacent the lower surface of the
plenum chamber 24, the upper marginal portion of the plenum chamber
is formed by an inverted dome-shaped perforated baffle 31. A vortex
inhibitor 29 is attached to the lower central portion of the dome
31 to control the rotation of the swirling mass of water entering
the perforations of the dome and to increase flow to the central
portion of the dome with a minimum of energy dissipation. In the
embodiment shown, the perforations 32 in the domed baffle are
substantially uniformly spaced in circular rows throughout the
extent of the domed baffle. Alternately, and if the occasion so
requires, the spacing of the perforations may be such as to
unequally distribute fluid flow upwardly from the plenum chamber 24
through the dome 31. The reasons for such a construction are
hereinafter described.
The structural support 23 attached to the core shield and
supporting the core elements is further provided with a
substantially flat perforated distributor plate 33 which in effect
forms a second plenum chamber 34 between the two plates. The flat
plate is likewise provided with uniformly spaced perforated holes
35 therein for distributed flow of fluid upwardly from the second
plenum chamber and into the flow channels formed in the reactor
core.
In the illustrated embodiment of the pressurized water reactor, the
reactor is designed for the flow of approximately 130 million
pounds of water per hour therethrough. This water has an incoming
temperature of approximately 555.degree. F. and an outlet
temperature of approximately 604.degree. F. The operating pressure
of the water utilized as a primary fluid in leaving the pressurized
reactor will be at 2,200 p.s.i.a. (pounds per square inch
absolute). At this pressure, saturation temperature of the water is
approximately 649.46.degree. F. leaving a margin below saturation
temperature of approximately 45.degree. F. This temperature
difference between operating temperatures and saturation
temperatures is considerably below that heretofore disclosed and is
intended to provide a margin of safety to avoid steam formation in
the primary fluid. It will be understood that this margin is
relatively narrow when considering the possible upsets of the
system both as to incoming temperature differences and as to flow
differences. Thus, it is highly desirable that the temperature of
the water entering each of the parallel flow passageways through
the reactor core should be substantially equal. Also, it is highly
desirable that the flow rates through each core-cooling channel
should be substantially uniform. By utilizing the distribution
system described, ordinary upsets in the overall system either as
to temperature or flow rates of the incoming water will not
ordinarily produce more than slight conditions of steam generation
within the reactor core.
In some installations it is possible that certain portions of the
reactor core may have a higher heat generation ability than other
portions of the core. Usually, such unbalance in heat output from
the reactor elements would be concentrated in the central portion
of the core. This might occur after a period of operation of the
unit where certain fuel cores have been replaced and the overall
reactivity of fuel elements in the core are unequal. When this is
contemplated it is possible to compensate for such unequal heating
by changes in the pattern of perforations in both the inverted
domed baffle 31 and the flat plate baffle 33 or either of them. The
illustrated arrangement contemplates substantially uniform
reactivity throughout the cross section of the core and accordingly
the baffles are uniformly perforated. It is, however, within the
contemplation of the present invention to provide an unbalanced
perforation in the baffles to compensate for unbalance in the
reactivity of portions of the nuclear reactor core.
* * * * *